Author/Authors :
Sagara، نويسنده , , A. and Motojima، نويسنده , , O. and Imagawa، نويسنده , , S. and Mitarai، نويسنده , , O. and Noda، نويسنده , , T. and Uda، نويسنده , , T. and Watanabe، نويسنده , , K. and Yamanishi، نويسنده , , H. and Chikaraishi، نويسنده , , H. and Kohyama، نويسنده , , A. and Matsui، نويسنده , , H. and Muroga، نويسنده , , T. and Noda، نويسنده , , N. and Ohyabu، نويسنده , , N. and Satow، نويسنده , , T. and Shishkin، نويسنده , , A.A. and Sze، نويسنده , , Dai-Kai and Suzuki، نويسنده , , A. and Tanaka، نويسنده , , S. and Terai، نويسنده , , T. and Yamazaki، نويسنده , , K. and Yamamoto، نويسنده , , J.، نويسنده ,
Abstract :
The main feature of FFHR is force-free-like configuration of helical coils, which makes it possible to simplify the coil supporting structure and to use high magnetic field instead of high plasma beta. The other feature is the selection of molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety. Collaboration works based on the LHD project have made great progress in the reactor studies by focusing on engineering aspects of the high magnetic field and Flibe system design. Encouraging positive results are shown on ignition access, mechanical stress in coils supporting structures, improvement in the blanket system including materials selection and tritium recovery. Critical issues on fundamental safety analysis and maintainability of reactor components are also discussed, and many subjects are pointed out as future works.
